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Journal ArticleDOI

Three-Dimensional Neutronic Calculations for the Fusion Breeder APEX Reactor

01 Jul 2007-Fusion Science and Technology (American Nuclear Society)-Vol. 52, Iss: 1, pp 107-115
TL;DR: In this paper, the nuclear characteristics of a fusion-fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, fissile fuel breeding, first wall radiation damage, and heat deposition have been investigated in a liquid first wall, blanket, and shield for the various mixture compositions of molten salt and heavy metals for blanket layer thicknesses of 20, 30, 40, and 50 cm.
Abstract: Three-dimensional analysis has been made using the MCNP Monte Carlo code and ENDF/B-VI nuclear data. The nuclear characteristics of a fusion-fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, fissile fuel breeding, first wall radiation damage, and heat deposition have been investigated in a liquid first wall, blanket, and shield for the various mixture compositions of molten salt and heavy metals for blanket layer thicknesses of 20, 30, 40, and 50 cm. The neutron flux load at the first wall is assumed to be 10 MW/ m 2 . The flowing molten salt wall is composed of flibe (Li 2 BeF 4 ) as the main constituent with increased mole fractions of heavy metals, 2 to 10% ThF 4 and UF 4 . In terms of all parameters, the mixtures with UF 4 show better performance than the mixtures with ThF 4 . The atomic displacement and the helium, tritium production rates remain well below the presumable limits for all mixture compositions of molten salt and heavy metals and thicknesses of the blanket.
Citations
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Journal ArticleDOI
TL;DR: In this article, ThF 4, UF 4 and UO 2 heavy metals were used with ratios of 2% and 10% while Flibe (Li 2 BeF 4 ) molten salt mixture and 100% Flibe were used as fluids in the liquid first wall, liquid second wall and shield zones of the APEX.

24 citations

Journal ArticleDOI
TL;DR: In this article, the effects of evaluated nuclear data files on neutronics characteristics of a fusion-fission hybrid reactor have been analyzed; three-dimensional calculations have been made using the MCNP4C Monte Carlo Code for ENDF/B-VII T ǫ=300 K, JEFF-3.0 T � = 300 K, and CENDL-2 T Â= 300 K evaluated nuclear files.

18 citations

Journal ArticleDOI
TL;DR: In this article, the three-dimensional Monte Carlo method was used to calculate the proton and He-4 gas production rates in the structural material of a fusion-fission hybrid reactor with the MCNPX-2.5 code.

16 citations

Journal ArticleDOI
TL;DR: In this paper, the effects of the selected fluid on the radiation damage, in terms of individual as well as total isotopes in the structural material, were investigated for 30 full power years.

11 citations

Journal ArticleDOI
TL;DR: In this paper, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 99-95% Li 20 Sn 80 -1-5% SFG-Pu, 99−95% L20 Sn 80 −1−5% SfGPuF 4, or 99− 95% L 20 Sn80 −1- 5% SFg-PUO 2, as fluids.

5 citations

References
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Journal ArticleDOI
TL;DR: In this paper, the authors explored novel concepts for fusion chamber technology that can substantially improve the attractiveness of fusion energy systems, including the potential for: (1) high power density capability; (2) higher plasma β and stable physics regimes if liquid metals are used; (3) increased disruption survivability; (4) reduced volume of radioactive waste; (5) reduced radiation damage in structural materials; and (6) higher availability.

319 citations

Journal ArticleDOI
TL;DR: In this article, the liquid-wall HYLIFE-II conceptual design has been presented, which has been shown to reduce the electricity cost by using a neutronically thick array of flowing molten-salt jets, which will not burn, has a low tritium solubility and inventory, and protects the chamber walls.
Abstract: Enhanced safety and performance improvements have been made to the liquid-wall HYLIFE reactor, yielding the current HYLIFE-II conceptual design. Liquid lithium has been replaced with a neutronically thick array of flowing molten-salt jets (Li[sub 2]BeF[sub 4] or Flibe), which will not burn, has a low tritium solubility and inventory, and protects the chamber walls, giving a robust design with a 30-yr lifetime. The tritium inventory is 0.5 g in the molten salt and 140 g in the metal of the tube walls, where it is less easily released. The 5-MJ driver is a recirculating induction accelerator estimated to cost $570 million (direct costs). Heavy-ion targets yield 350 MJ, six times per second, to produce 940 MW of electrical power for a cost of 6.5 cents/kW[center dot]h. Both larger and smaller yields are possible with correspondingly lower and higher pulse rates. When scaled up to 1934 MW (electric), the plant design has a calculated cost of electricity of 4.5 cents/kW[center dot]h. The design did not take into account potential improved plant availability and lower operations and maintenance costs compared with conventional power plant experience, resulting from the liquid wall protection. Such improvements would directly lower the electricity cost figures. For example,more » if the availability can be raised from the conservatively assumed 75% to 85% and the annual cost of component replacement, operations, and maintenance can be reduced from 6% to 3% of direct cost, the cost of electricity would drop to 5.0 and 3.9 cents/kW[center dot]h for 1- and 2-GW (electric) cases. 50 refs., 15 figs., 3 tabs.« less

273 citations

Journal ArticleDOI
TL;DR: New and ‘revolutionary’ concepts that can provide the capability to efficiently extract heat from systems with high neutron and surface heat loads while satisfying all the FPT functional requirements and maximizing reliability, maintainability, safety, and environmental attractiveness are explored.

139 citations

Journal ArticleDOI
TL;DR: Conditions necessary to achieve deuterium-tritium fuel selfsufficiency in fusion reactors were derived through extensive modeling and calculations of the required and achievable tritium breeding as discussed by the authors.
Abstract: Conditions necessary to achieve deuterium-tritium fuel self-sufficiency in fusion reactors are derived through extensive modeling and calculations of the required and achievable tritium breeding ra...

120 citations

Journal ArticleDOI
TL;DR: In this paper, the potential of achieving tritium self-sufficiency depends on many system physics and technology parameters, and Interactive Physics and Technology R&D programs should be implemented to determine the potential to realize those physics and technologies options and parameters that have large effects on attaining a realistic window for tritiam self-sufficiency.

115 citations

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